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EXPERIMENTS ON NONLINEAR VIBRATIONS OF A NUCLEAR FUEL ROD SUPPORTED BY SPACER GRIDS IN AIR AND SUBMERGED IN WATER

机译:空气中隔水栅支撑并浸入水中的核燃料棒的非线性振动实验

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For safety reasons, the nuclear fuel assemblies of Pressurized Water Reactors (PWR) must be able to withstand external excitations ranging from large amplitude seismic motions of the reactor to flow-induced vibrations from the surrounding coolant water. A nuclear fuel assembly is composed of long slender tubes, most of them filled with uranium pellets, maintained in a square array by spacer grids. The spacer grids provide a nonlinear flexible boundary condition with friction and micro-impacts that complicates the nonlinear dynamics. In order to improve safety margins in the design of nuclear fuel assemblies, it is of great interest to understand the influence of the spacer grids, as it relates to the overall structural stiffness and damping properties. In particular, the evolution of the vibration amplitude with increasing excitation forces is still undetermined. In order to understand the nonlinear vibration response of a zirconium fuel rod filled with nuclear fuel pellets and supported by spacer grids, experiments were carried out in water and in air. They consisted of measuring the vibration response of the rod under a step-sine harmonic excitation at different force amplitude levels in the frequency neighborhood of the fundamental mode. If the excitation is large enough, the response of the rod displays nonlinear phenomena such as the shift of the resonant frequencies, multiple solutions with instabilities (jumps) and hysteresis, and one-to-one internal resonances. These experiments were carried out on zirconium tubes filled with axially unconstrained as well as axially blocked metallic pellets, which simulate the nuclear fuel. The zirconium tubes were tested both in air and immersed in water. The experimental data will be processed in the future by means of an identification procedure to extract the nonlinear stiffness and damping parameters of the system. An increase of the equivalent viscous damping with the excitation amplitude level is expected.
机译:出于安全原因,压水堆(PWR)的核燃料组件必须能够承受外部激励,从反应堆的大振幅地震运动到周围冷却水的流动引起的振动。核燃料组件由细长的长管组成,其中大部分装有铀粒,并通过隔离栅保持正方形排列。间隔栅提供了带有摩擦和微冲击的非线性柔性边界条件,使非线性动力学复杂化。为了提高核燃料组件设计的安全裕度,非常了解间隔条的影响,因为它与整体结构的刚度和阻尼特性有关。特别地,仍未确定振动振幅随激振力的增加而变化。为了理解填充有核燃料芯块并由间隔栅支撑的锆燃料棒的非线性振动响应,在水和空气中进行了实验。它们包括在基本模式的频率邻域中,在不同的力幅值水平下,在步进正弦谐波激励下测量杆的振动响应。如果激励足够大,则杆的响应将显示非线性现象,例如共振频率的偏移,具有不稳定性(跳跃)和磁滞的多个解以及一对一的内部共振。这些实验是在装有轴向不受约束以及轴向受阻的金属小球的锆管上进行的,这些金属小球模拟了核燃料。锆管在空气中和浸入水中均进行了测试。将来将通过识别程序来处理实验数据,以提取系统的非线性刚度和阻尼参数。预计等效粘性阻尼随激励振幅水平的增加而增加。

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